Training simulator for nuclear power plant reactor monitoring

ABSTRACT

A method and apparatus for the real-time dynamic simulation of a nuclear power plant that includes a control and nuclear instrumentation console for operating the reactor and monitoring three-dimensional physical values in the reactor core. A digital computer is connected to the console to calculate physical values such as nuclear flux, power, and temperature including the distribution thereof throughout the core with such calculations including the effect of full length, part length, and malfunctioned reactor control rods, as well as xenon, decay heat and boron, for example, on the output and distribution of power within the core. The simulation also includes instrumentation that responds to the calculated physical values by recording a continuous trace of the flux value in the reactor core from the top to the bottom.

United States Patent 11 1 1111 3,916,444

Alliston et al. 5] Oct. 28, 1975 TRAINING SIMULATOR FOR NUCLEAR PrimaryExaminer-Malcolm A. Morrison POWER PLANT REACTOR MONITORING AssistantExaminerEdward J. Wise [75] Inventors: William H. Alliston, Murrysville;Attorney Agent or FlrmH' Patterson Francis R. Czerniejewski, Glenshaw;

Boris A. Mutafelija, Allison Park, all [57] ABSTRACT of Pa- A method andapparatus for the real-time dynamic Assigneel Westinghouse ElectricCorporation, simulation of a nuclear power plant that includes aPittsburgh, control and nuclear instrumentation console for oper [22]Filed: Feb. 23, 1973 ating the reactor and monitoring three-dimensionalphysical values in the reactor core. A digital computer PP 335,181 isconnected to the console to calculate physical values such as nuclearflux, power, and temperature in- 52 us. c1. 444/1; 176/19; 35/13 cludingthe distribution thereof throughout the Core [5]] Int G015/06;GO6f15/56;G09b 9/00 with such calculations including the effect offull [58] Field of Search H 444/1; 235/184; 176/19 length, part length,and malfunctloned reactor control 176/24. 35/10 13 102 rods, as well asxenon, decay heat and boron, for ex 7 ample, on the output anddistribution of power within [56] References Cited the core. Thesimulation also includes instrumentation UNITED STATES PATENTS thatresponds to the calculated physical values by recording a continuoustrace 01f the flux value in the re- 3,06l,945 l 1/1962 Hawkins 35/10 a tr ore from the top to the bottom. 3,237,318 3/1966 Schager 33 Claims, 40Drawing Figures GNc CSP CONTAINMENT BUILDING SYSTEM TURBINE CONTROLLERIS LOW REACTOR VESSEL MAIN | L CONTROL OFFICE I H f |4 H H i lmlziwtktfie NISP I ESSP\ cmcwmv Q NUCLEAR ENGINEERED REACTOR CONTROL 111TURBINE 8- MAIN GENERATOR CONTROL INSTRUMENTATION SAFEGUARDSINSTRUMENTATION SYSTEM PANEL SYSTEM PANELS SYSTEM PANELS BALANCE OFPLANT PANELS U.S., Patent Oct. 28, 1975 Sheet 3 0131 A $916,444

FIG. QO/IA DETECTOR POSITION CABLE POSITION INSERTED WITHDRAWN OPERATIONSELECTOR A SET SET BOTTOM LIMIT TTOP LIMIT -Q DETI 'EIIFTIOR O I O 0OSTORAGE SELSWG PATH SESLECTOR COMMON GROUP EMERGENCY STORAGEEEEIIEIIIIIIIZ] 2Q CALIBiRATE DETECTOR READOUT FUSES m A RECORDER O O oo O O Q VOLTS ADJUST 50o INDICATOR NEG. EXT. I50 I I50 ON m 50$ /so I. Il I l 1 L I i l I U EN ORDER FMAP EN EACH DETECTOR TCCHAN TCCHAN TCCHANRANGE TCOUPL TCCHAN l 2 3 4 6 7 O O O O O O O O O O O O :3 I:

US. Patent Oct.28, 1975 Sheet40f31 3,916,444

A B 'c o (I; T I T T M N o I I O O 2 O' O O 3 O O O O 4 OO O O O O O -OO O 'O O O O O O *O O O O O OOO O O O O O O O *O O O O O O O l3 Q Q C) OO O O [5 O 0 FIG. 90/IB US. Patent Oct. 28, 1975 Sheet 5 of 31 3,916,444

COMMON CONTROLS Q 'X E B C D STOP INSERT SCAN RECORD WITHDRAW A0 I E O GO C) 0 POWER OI 'F SPEED OF R ,ON AUTO ,M AN. g gx' ow\ H1 POWERDiSTRlBUTlON m0 SUP 2AMP ii GD QDGD 0 RECORDERS ALARM I AMP FUSE RESETQDQDQD ROD DISCONNECT FIG. 90/!0 U.S. Patent Oct. 28, 1975 Sheet7Of31 A3,916,444

DETECTO R CUR RENT COMPARATOR Elli! U UK] [I] [I] Q Q B UPPER SECTIONLOWER SECTION NORMAL Q Q NORMAL BYPASSlBYPASS AUDIO SPEAKER AUDIO O QMULTIPLIER yQLi MIN MAX.

FIG. 90/25 US. Patent Oct. 28, 1975 Sheet I0 of 31 3,916,444

TH ERMOCOUPLES PROTECT ION CHANNEL I B DECTECTORS POWER RANGE ADETECTORS POWER RANGE PROTECTION CHANNEL 11 INTERMEDIATE RANGE DETECTORFUEL ROD (5 LENGTH US. Patent 0ct.28, 1975 Sheet 11 of 31 3,916,444

ROD POSITIONS N m 4 m WM W W 0U ww mm W m m F e 1 1 W .N T T 5 R W W m TR" R E mmU MW E E NW 6 D AP D D A 9 R RN T R R O ODS.OEOD G E W 1 9 E WH N" SM N 6A C 2 L 0 2 L O E C E C \l RD 10 l I v vm H L l 2/ I F1 T T1||1 ||||1 N N N E O E N 0T N O OE m .|1|| .l||1 D.- RSL M FU M /1 0 NF0 C XOL m A VI X C O0 CHAMBER #l PRIMARY SHIELD FlG.96/3

IN CORE DETECTOR U.S. Patent Oct. 28, 1975 Sheet 12 of31 3,916,444

UNRODDED 9 l 6 9 W F I I T UNRODDED FUEL HOLDER DEPRESSIONSUNRODDED(LOWER POWER) RODS TRANSITION FUNCTION DEP ROD DEPRESSIONI FIG.96/IO IZO IOO

US. Patent Oct. 28, 1975 Sheet 13 of 31 mimmdl 0 0 O v Ow Om: Om

Ow OW O N r OON JmZZ IO Z 00m I US. Patent CURROD BEGIN LOOP FOR NgRMALCONVERT CONVERT POSITIONS TO I20 MESH END g LOOP BEGIN LOOP FOR ALL RODSLIMIT ROD POSIFTION 0 I20 STEPS END GE) END FIG. 96/!4 Oct. 28, 1975Sheet 14 of 31 GET UPPER AND LOWER INDICIES ON I20 POINT MESH FORTRANSITION FUNCTION APPLICATION GET UPPER AND LOWER INDICIES ON I20POINT MESH CONSTRAIN INDICIES AT UPPER AND LOWER CORE BOUNDRIES (I ANDI20) BEGIN LOOP FOR TRANSITION FUNCTION JJ= ABSOLUTE mogx CONSTRAININDICIES AT UPPER AND LOWER CORE BOUNDRIES (I AND I20) APPLY TRANSITIONFUNCTION WITH PROPER REDUCTIONS FOR FACE AND CORNER RODS APPLY DEEP RODDEPRESSION FACTOR END LOOP END F IG. 96/I5 BEGIN LOOP FOR FUNCTIONAPPLICATION FIG. 96/ I6 CALCULATE DISTANCE FROM CENTER TO PROBE CALCULATE ANGLE OF PROBE TILT FUNCTION BASED ON MALFUNCTION ROD BI PROBE FIG.96/ I7 US. Patent Oct. 28, 1975 Sheet 16 of 31 P2300 00m mwzmou 7 OF 5041O wwom US. Patent' 00. 28, 1975 Sheet 17 of 31 3,916,444

DETECTOR OP SELECT NOTE: TL407X TRUE IS POSITION AT NORMAL; FALSE IFPOSITION AT STORAGE (O OH I ('I OH msmorq 2 100.0

CO NORMAL I C! NORMAL .AND. TL407X CO STORAGE Cl STORAGE .AND. NOT.TL407X LOGTDT TL407X 2.5 SEC LOGTOF TL407X 10.0 SEC FIG. 96/l9 US.Patent Oct. 28, 1975 Sheet 18 of 31 3,916,444

DETECTOR PATH SELECT TD VARIABLE I FALSE PATH l (,1, PATH 2 CT. I FALSLI TRUE PATH '1 GI PATH 3 (IL I FAlSi I TRUT PATHJCL PATHlGL I FALSE ITRUE PATH 4 GL PATH 5 GL I FALSE I TRUE PATH SOL PATHGGL I VAlST l TRUEPATH 6 (3L PATH 7 CL I FALSE I TRUE PATH 7 GL PATH 8 GL I FALSE I TRUEPATH 8 GL PATH 9 GL I FALSE I TRUE PATH 9 GL PATH 0 GI. IFALSE I TRUEPATH l0 GL PATH l GL TO VARIABLE I FALSE I TRUE I FALSE FIG. 96/2OA US.Patent Oct.28, 1975 Sheet 19 0f31 3,916,444

PAIN (.0'. (I-vo) vosmcm PAmcfi (l|0) 700.0 .AND. PATH CL 0-10) mm PATHcm (l-IO) MAIN PAIN PAIN cu co nus: l-lo) [IMP Wu! IF MP m1! IF I bl AN!PAIN co u-lo) IS mm MAIN PAIN I: (u I "MP .LQQL L H) VARIAMI OSIIIONI97.|

CALL CHAIN CALL CHAIN PAIN SELC OI SELECI POSIHON CHG Gl I YRUEINSERT/WUN 25 WHHDNAW CO WIYHDI GL l FALSE POSITION FIG. 96/268

1. An automated training simulator for the real-time dynamic operationof a nuclear powered electrical generating plant; comprising a pluralityof manually operable devices corresponding to reactor control devices;storage means for storing a first plurality of data values correspondingto spaced locations along one axis of a simulated core and for storing asecond plurality of data values corresponding to spaced locations alongsecond axes in a plane normal to the one axis; calculating meansincluding sequence controlling means having the following components a.means governed by the operation of the control devices and the firstplurality of data values to generate a third datA value for each ofpredetermined spaced locations along the one axis to determine theeffect of control device operation along the one axis, b. means governedby the operation of the control devices and the second plurality of datavalues to generate a fourth data value for each of predetermined ones ofthe stored second data values to determine the effect of control deviceoperation along the second axes, and c. means governed by the third andfourth data values to generate fifth data values for a selected portionof the reactor core; and indicating means responsive to the fifth datavalues to monitor the operation of the reactor at positions includingpositions spaced from the first and second axes.
 2. An automatedtraining simulator according to claim 1 wherein the second plurality ofdata values corresponds to spaced locations along a second axis normalto the first axis and along a third axis and perpendicular to the secondaxis of the reactor core.
 3. An automated training simulator accordingto claim 2 wherein the one axis represents a vertical axis through thecenter of the simulated core and the second and third axes represent ahorizontal axis.
 4. An automated training simulator according to claim 1wherein the first plurality of data values include data relating toreactor flux production, absorption, and velocity for each spacedlocation.
 5. An automated training simulator according to claim 1wherein the first plurality of data values include data relating topower per fission and a diffusion coefficient at each spaced location.6. An automated training simulator according to claim 1 wherein thefirst plurality of data values include data relating to nuclear flux ateach spaced location.
 7. An automated training simulator according toclaim 1 wherein the second plurality of data values relate to dataincluding total reactor power, and a critical bias for the firstplurality of data values.
 8. An automated training simulator accordingto claim 1 wherein the second plurality of data values include datarelating to boron concentration and xenon at the spaced locations alongthe second axes.
 9. An automated training simulator according to claim 1wherein said calculating means are structured in a digital computermeans.
 10. An automated training simulator for a nuclear power plant;comprising a console device having control devices for selectivelycontrolling the movement of a flux detector in a reactor core; a devicefor recording a map of the flux value through the length of a reactorcore along a predetermined path in response to signals representative ofdetected flux; and calculating means including sequence controllingmeans having the following components a. means to generate a data valuerelating to neutron flux at each of a plurality of spaced locationsalong a predetermined axis of the core substantially parallel to thepredetermined path, b. means governed by the flux detector controldevices to generate data representative of the position of a neutronflux detector in the reactor core in response to the operation of theconsole control devices, and c. means governed by the generated datarepresentative of detector position to generate signals representativeof detector flux in the predetermined path to operate the recordingdevice in accordance with each generated flux data value sequentially.11. An automated training simulator according to claim 10 wherein therecording device responds to each generated neutron flux data valuesequentially during substantially equally spaced time intervals.
 12. Anautomated training simulator according to claim 10 wherein the meansincluding the calculating means is structured in a programmed digitalcomputer means.
 13. An automated training simulator for the dynamicoperation of a nuclear powered electrical generating plant; comprising aplurality of manually operable devices corresponding to control devicesfor operating the plant; and calculating means including sequencecontrolling means having the following components a. means governed bythe operation of selected devices to generate first data values for eachof a plurality of spaced locations along a first axis of a nuclearreactor, b. means governed by the operation of selected devices togenerate data values for each of a plurality of spaced locations in thereactor in a plane normal to the first axis, c. means governed byselected ones of the first and second generated data values to generatethird data values representative of physical values at locations spacedfrom the first axis and said plane; and indicating means governed by thethird data values to monitor physical values relating to the conditionof a reactor in three dimensions at locations spaced predetermineddistances from the first axis and said plane.
 14. An automated trainingsimulator according to claim 13 wherein the third data values aregenerated repetitively for each successive spaced location along apredetermined detector path, which path is spaced from the one axis; theindicating means is a recording device governed by each of the generatedthird data values in succession to trace the nuclear flux values alongsaid detector path; the selected control devices are operable to commandpositions relating to the position of a control rod such that fluxdistribution is asymmetrical along the first axis; the second datavalues include a. data values relating to the location of each of aplurality of said detector paths relative to an angle having a referenceaxis in the plane and its distance from the first axis, and b. datavalues relating to the coefficient effect of the commanded rod position;and the third data values include data values relating to theattenuation of nuclear flux along said path.
 15. An automated trainingsimulator according to claim 14 wherein the data value relating to thecoefficient effect is calculated according to the formula
 16. Anautomated training simulator according to claim 15 wherein saidcalculating means are structured in a digital computer means.
 17. Anautomated training simulator according to claim 14 wherein saidcalculating means are structured in a digital computer means.
 18. Anautomated training simulator according to claim 13; wherein the sequencecontrolling means includes a. means to generate for each of the spacedlocations along the first axis data relating to cross-sectional valuesin accordance with the operation of selected devices and data valuesrelating to total reactor core power, b. means to generate for each ofthe spaced locations along the first axis a data value relating tonuclear flux in accordance with the first data values includingcross-sectional data values, nuclear flux and reactor critical bias,said critical bias data value being a ratio of a data value relating tonuclear production and nuclear flux absorption, and c. means to generatea data value relating to total reactor power in accordance with thegenerated data values relating to nuclear flux.
 19. An automatedtraining simulator according to claim 18; wherein the sequencecontrolling means further comprising a. means to generate for each ofthe plurality of spaced locations along the first axis a datA valuerelating to delayed neutrons in accordance with data values includingthe generated data values relating to neutron flux, b. means to generatefor each of the spaced locations along the first axis a data valuerelating to fuel temperature in accordance with the generated data valuerelating to total power, and c. means to generate for a first portion ofthe spaced locations along the first axis a data value relating toaverage power, and d. means to generate for a second portion of thefirst spaced locations along the first axis a data value relating toaverage power, both said data values being generated in accordance withthe generated data values for each of the spaced locations along thefirst axis relating to reactor power.
 20. An automated trainingsimulator according to claim 19 wherein said calculating means arestructured in a digital computer means.
 21. An automated trainingsimulator according to claim 18 wherein said calculating means arestructured in a digital computer means.
 22. An automated trainingaccording to claim 13 wherein the first axis extends vertically throughthe center of the reactor core.
 23. An automated training simulatoraccording to claim 13 wherein the plane includes a second axisperpendicular to a third axis, and the second data values are generatedwith respect to their location from the first, second, and third axes.24. An automated training simulator according to claim 13 wherein theindicating means include devices to indicate water temperature atselected locations spaced from the first axis.
 25. An automated trainingsimulator according to claim 13 wherein the first data values relate tonuclear flux value for each of the plurality of spaced locations.
 26. Anautomated training simulator according to claim 13 wherein the seconddata values are coefficients that correspond to the influence of amalfunctioned rod on the first data values.
 27. An automated trainingsimulator according to claim 13 wherein the indicating means include theindication of data values at positions spaced from and in a plane normalto the one axis; and the selected control devices are operative torepresent the position of a reactor control rod resulting in anasymmetrical flux distribution; and said sequence controlling meansincludes a. means to generate a data value corresponding to an anglebetween the one plane and another plane which corresponds to theinfluence of a malfunctioned rod on flux distribution in the directionof the means, and b. means to generate a data value corresponding to acoefficient representative of the influence of a malfunctioned rod onthe flux distribution adjacent the indicated positions.
 28. An automatedtraining simulator according to claim 27 wherein the data value relatingto said angle is in accordance with a second order curve fit as afunction of distance from the first axis.
 29. An automated trainingsimulator according to claim 28 wherein said calculating means arestructured in a digital computer means.
 30. An automated trainingsimulator according to claim 27 wherein the indicating means includesmeans to respond to generated data for detecting values on oppositesides of the first axis in a plane normal to the first axis; and thecalculation of the coefficient corresponds to the formula X d COS G Y dSIN G where X represents the coefficient a second axis, Y represents thecoefficient for a third axis in said plane, d represents the distancefrom the first axis, and G represents the angle between a malfunctionedrod position and the said second and third axes.
 31. An automatedtraining simulator according to claim 30 wherein said calculating meansare structured in a digital computer means.
 32. An automated trainingsimulator according to claim 27 wherein said calculating means arestructured in a digital computer means.
 33. An automated trainiNgsimulator according to claim 13 wherein said calculating means arestructured in a digital computer means.